A5086841146- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Nuclear and radioactivity studies
- Nuclear Physics and Applications
- Graphite, nuclear technology, radiation studies
- Nuclear Engineering Thermal-Hydraulics
- Fusion materials and technologies
- Heat transfer and supercritical fluids
- Radioactive contamination and transfer
- Risk and Safety Analysis
- Molten salt chemistry and electrochemical processes
- Magnetic confinement fusion research
- Particle accelerators and beam dynamics
- Radioactive element chemistry and processing
- Environmental and Sediment Control
- Advanced Mathematical Modeling in Engineering
- Smart Grid Security and Resilience
- Smoking Behavior and Cessation
- Superconductivity in MgB2 and Alloys
- Anxiety, Depression, Psychometrics, Treatment, Cognitive Processes
- Heat Transfer and Boiling Studies
- Spacecraft Design and Technology
- Heat Transfer and Optimization
- Carbon Dioxide Capture Technologies
- Fatigue and fracture mechanics
Idaho National Laboratory
2019-2024
Oak Ridge National Laboratory
2010-2023
Mayo Clinic in Arizona
2013
Office of Scientific and Technical Information
1999-2012
National Technical Information Service
2009-2012
Office of Nuclear Energy
2012
Argonne National Laboratory
2012
British Nuclear Fuel Limited (United Kingdom)
2004
Computational Physics (United States)
1995
Massachusetts Institute of Technology
1992
This paper describes the methodology developed and implemented in Virtual Environment for Reactor Applications Core Simulator (VERA-CS) to perform high-fidelity, pressurized water reactor (PWR), multicycle, core physics calculations. Depletion of with pin-resolved power nuclide detail is a significant advance state art analysis, providing level necessary address problems U.S. Department Energy Nuclear Simulation Hub, Consortium Advanced Light Water Reactors (CASL). VERA-CS has three main...
A study on the Fukushima Daiichi nuclear power station spent-fuel pool (SFP) at Unit 4 (SFP4) is presented in this paper. We discuss design characteristics of SFP4 and its decay heat load detail provide a model that we developed to estimate SFP evaporation rate based temperature. The level following March 11, 2011, accident predicted fundamental conservation laws mass energy. Our temperatures are good agreement with measured data consistent Tokyo Electric Power Company evaluation results.
Molten salt reactors (MSRs) represent a class of that use liquid salt, usually fluoride based or chloride based, as either coolant with solid fuel (such salt–cooled high-temperature reactors) combined and the dissolved in carrier salt. For liquid-fueled MSRs, can be processed online batch mode to allow for removal fission products well introduction fissile fertile materials during reactor operation. The MSR is most commonly associated 233U/thorium cycle, nuclear properties 233U parasitic...
An assessment of advanced reactor technology options was conducted to provide a sound comparative technical context for future decisions by the U.S. Department Energy (DOE) concerning these technologies. Strategic objectives were established that span wide variety important missions, and needs identified based on recent DOE international studies. A broad team stakeholders from industry, academia, government assembled develop comprehensive set goals, criteria, metrics evaluate irradiation...
AbstractAbstractThis study evaluated the neutronics and some of fuel cycle characteristics using uranium-based fully ceramic microencapsulated (FCM) in a pressurized water reactor (PWR). Specific PWR lattice designs with FCM have been developed that are expected to achieve higher specific burnup levels while also increasing tolerance accidents. The SCALE software system was primary analysis tool used model designs. A parametric performed by varying tristructural isotropic particle design...
This work provides a summary of selected experimental capabilities being developed to support nonnuclear testing and demonstration technology in microreactors under the U.S. Department Energy's (DOE's) Microreactor Program. Major include Single Primary Heat Extraction Removal Emulator (SPHERE) Agile Non-nuclear Experimental Test Bed (MAGNET). The SPHERE facility allows for controlled steady-state transient heat rejection single pipe using electrical heaters that simulate nuclear heating. is...